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English: Generation II nuclear reactor vessel sizes of similar power output: PWR: typical Westinghouse 4 loop reactor pressure vessel (3411MWt, 1125MWe). CANDU: Darlington reactor calandria (2657MWt, 935MWe). BWR-4 reactor pressure vessel (3293MWt, 1098MWe). RBMK-1000 reactor steel vessel, biological shields, and water tank (3200MWt, 1000MWe).
English: Schematic diagram of an Advanced Gas-cooled Reactor type nuclear reactor 1. Charge tubes 2. Control rods 3. Graphite moderator 4. Fuel assemblies 5. Concrete pressure vessel and radiation shielding 6. Gas circulator 7. Water 8. Water circulator 9. Heat exchanger 10. Steam
It houses the vessel of the reactor, which is annular, made of an inner and outer cylindrical wall and top and bottom metal plates that cover the space between the inner and outer walls, without covering the space surrounded by the vessel. The reactor vessel is an annular steel cylinder with hollow walls and pressurized with nitrogen gas, with ...
The reactor buildings of Bradwell magnox nuclear power station. The magnox reactors were considered at the time to have a considerable degree of inherent safety because of their simple design, low power density, and gas coolant. Because of this they were not provided with secondary containment features. A safety design principle at the time was ...
A reactor vessel head for a pressurized water reactor. This structure is attached to the top of the reactor vessel body. It contains penetrations to allow the control rod driving mechanism to attach to the control rods in the fuel assembly. The coolant level measurement probe also enters the vessel through the reactor vessel head.
The core thermal power was 626 MWt. The reactor vessel was rated to 1015 psia and measured 12 feet 2 inches (3.71 m) diameter and 42 feet (13 m) tall. Dresden 1 Nuclear Flow Diagram featured a secondary steam generator for load following. The reactor featured a dual cycle, with steam coming from both the stream drum and steam generators.
GE further developed the BWR-1 design with the 70 MW Big Rock Point (9×9, 11×11, 12×12) reactor, which (like all GE BWR models following Dresden 1) used the more economical direct cycle method of heat transfer, but disposed with the external recirculation pumps in favor of natural circulation (an unusual strategy that only the 55 MW ...
The VVER-TOI reactor pressure vessel has fewer welds than the VVER-1200, all out of the central area, and a more symmetric arrangement of coolant nozzles. This gives the potential for two 20 year life extensions, which could give a 100 year life.